GB1397723A - Guide structure for control elements - Google Patents
Guide structure for control elementsInfo
- Publication number
- GB1397723A GB1397723A GB3089873A GB3089873A GB1397723A GB 1397723 A GB1397723 A GB 1397723A GB 3089873 A GB3089873 A GB 3089873A GB 3089873 A GB3089873 A GB 3089873A GB 1397723 A GB1397723 A GB 1397723A
- Authority
- GB
- United Kingdom
- Prior art keywords
- core
- coolant
- tubes
- control elements
- plenum
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
Abstract
1397723 Controlling reactors; emerging core cooling systems COMBUSTION ENG Inc 28 June 1973 [28 June 1972] 30898/73 Heading G6C A guide structure for aligning fuel assemblies in a pressurized water reactor core, and for guiding a plurality of control elements for telescoping movement within guide channels in the fuel assemblies, comprises two spaced tube sheets 80, 82 rigidly connected by a plurality of hollow tubes 84 which extend between them and supported by a flange 87 of a support barrel 86 on a lip 52 of the reactor vessel 22, hanging within a core barrel 48 which is itself supported by a flange 50. Each of the hollow tubes 84 is in alignment with a guide tube 32 in a fuel assembly. The primary or shutdown control element assemblies 56, 58 each comprise a plurality of high worth control elements 102 gauged together by means of a yoke 96, 98 resectively connected to a drive rod extension 62 by couplings 100. The assembly 56 is 4-fingered and the assembly 58 is 8-fingered. The drive mechanisms for these assemblies are electromagnetic linear motion drive devices which move the control elements 102 in incremental steps into and out of the reactor core. The fine grain control element assemblies 60 each comprise a single low worth control element (104), (Fig. 6, not shown), completely and individually enshrouded above the reactor core by shrouds or tubing 92 coupled by piping 64 through a single nozzle in the vessel head with an hydraulic actuator which maintains the control elements (104) in either a fully inserted or fully retracted position. The water coolant enters the reactor vessel 22 through inlet nozzles (75), (Fig. 1, not shown), and passes down between the vessel 22 and the core barrel 48, then up through the reactor core into an outlet plenum 74, and finally outwardly through openings 168 in the core barrel 48 and outlet nozzles 76. The outlet plenum 74 is a high cross flow region wherein the coolant is turned to pass through the outlet nozzles 76 and the control elements 102, 104 are shielded from the adverse effects of this high cross flow by the tubes 84 each of which enshrouds one of the control elements. The yokes 96, 98 always remain above the upper tube sheet 82 and are thus never subjected to this high cross flow. Protective shrouds 88, 90 for the gauged control element assemblies 56, 58 are provided above the upper tube sheet 82 and serve to prevent outward bowing of the control elements 102 which might otherwise interfere with the effective insertion of adjacent control element assemblies in the event of an emergency. The fuel assemblies have hollow alignment posts 38 in registry with the upper ends of the guide tubes 32 and these posts 38 enter the lower ends of the tubes 84. The guide structure can be adapted to provide an emergency core cooling system which provides sufficient coolant flow to remove the decay heat should a break occur in the normal coolant system. Emergency core coolant is introduced into an inactive plenum 78 above the upper tube sheet 82 and, as shown in Fig. 10, passes into the outlet plenum 74 via pipes 196 to aid in condensing steam which will then fall back as water into the core 26. Tubes 194 similar to the tubes 84 by-pass the plenum 74 and serve to spray the coolant directly on to the fuel assemblies 28 and their fuel elements 30. Coolant also passes through the tubes 84 and into the guide tubes 32 of the fuel assemblies 28, these latter tubes being provided with holes 200 in the lower region of the core 26 whereby the coolant by-passes the plenum 74 and a substantial portion of the core 26. Steam in the outlet plenum 74 is released into the inactive plenum 78 via pipes 198 where it is condensed by the emergency coolant. A system is also described (Fig. 11, not shown) which by using pressurized emergency coolant can overcome any possible steam blockage occurring in the upper region of the core.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US00266858A US3849257A (en) | 1972-06-28 | 1972-06-28 | Guide structure for control elements |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1397723A true GB1397723A (en) | 1975-06-18 |
Family
ID=23016271
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB3089873A Expired GB1397723A (en) | 1972-06-28 | 1973-06-28 | Guide structure for control elements |
Country Status (7)
Country | Link |
---|---|
US (1) | US3849257A (en) |
JP (1) | JPS5347880B2 (en) |
CA (1) | CA992672A (en) |
ES (1) | ES416637A1 (en) |
FR (1) | FR2202339A1 (en) |
GB (1) | GB1397723A (en) |
SE (1) | SE384289B (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE3023992A1 (en) * | 1979-07-02 | 1981-01-29 | Babcock & Wilcox Co | BRACKET FOR A CORE REACTOR CONTROL DEVICE |
Families Citing this family (37)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE2310080A1 (en) * | 1973-02-28 | 1974-08-29 | Siemens Ag | BOILING WATER REACTOR |
CA1027679A (en) * | 1973-07-31 | 1978-03-07 | Walter E. Desmarchais | Emergency core cooling system for a nuclear reactor |
US3976834A (en) * | 1974-03-25 | 1976-08-24 | Combustion Engineering, Inc. | Emergency core cooling injection manifold |
AT369179B (en) * | 1974-04-10 | 1982-12-10 | Kraftwerk Union Ag | DETACHABLE IN A REACTOR PRESSURE TANK |
US4050986A (en) * | 1974-09-13 | 1977-09-27 | The United States Of America As Represented By The United States Energy Research And Development Administration | Nuclear reactor I |
JPS51140090A (en) * | 1975-05-30 | 1976-12-02 | Hitachi Ltd | Fuel aggregate |
US4073684A (en) * | 1976-09-27 | 1978-02-14 | Combustion Engineering, Inc. | Releasable extension shaft coupling |
DE3008442A1 (en) * | 1980-03-05 | 1981-09-10 | Kraftwerk Union AG, 4330 Mülheim | FUEL ELEMENT FOR A CORE REACTOR |
DE3009937A1 (en) * | 1980-03-14 | 1981-09-24 | Kraftwerk Union AG, 4330 Mülheim | High converter reactor in pressurised water reactor vessel - occupies lower core zone and has absorber rods with common drive |
US4832899A (en) * | 1980-12-16 | 1989-05-23 | Westinghouse Electric Corp. | Mechanical spectral shift reactor |
FR2501892B1 (en) * | 1981-03-13 | 1985-10-25 | Framatome Sa | NUCLEAR REACTOR WITH DEVICE FOR GUIDING THE CONTROL CLUSTERS |
FR2516691A1 (en) * | 1981-11-13 | 1983-05-20 | Framatome Sa | DEVICE FOR GUIDING A NUCLEAR REACTOR CONTROL CLUSTER |
JPS59151132U (en) * | 1983-03-29 | 1984-10-09 | 明星電気株式会社 | pressure gauge |
US4659539A (en) * | 1983-04-29 | 1987-04-21 | Westinghouse Electric Corp. | Nuclear reactor |
US4716013A (en) * | 1983-04-29 | 1987-12-29 | Westinghouse Electric Corp. | Nuclear reactor |
FR2547100B1 (en) * | 1983-06-03 | 1985-08-30 | Framatome Sa | GUIDANCE DEVICE FOR NUCLEAR REACTOR CONTROL CLUSTERS |
JPS62152704A (en) * | 1985-12-27 | 1987-07-07 | 株式会社 湊組 | Manufacture of mortar lining steel pipe |
JPS62152705A (en) * | 1985-12-27 | 1987-07-07 | 技術資源開発株式会社 | Steel-pipe mortar lining device |
FR2595501B1 (en) * | 1986-03-07 | 1988-06-10 | Framatome Sa | INTERNAL EQUIPMENT OF NUCLEAR REACTORS WITH EXTENDED TANK |
US4759904A (en) * | 1986-04-04 | 1988-07-26 | Westinghouse Electric Corp. | Pressurized water reactor having improved calandria assembly |
US4902468A (en) * | 1987-10-21 | 1990-02-20 | Westinghouse Electric Corp. | Control rod support having planar wear surfaces |
FR2627321B1 (en) * | 1988-02-11 | 1992-08-14 | Framatome Sa | SUPERIOR INTERNAL EQUIPMENT OF NUCLEAR REACTOR PROVIDED WITH A FLOW SEPARATION DEVICE |
JPH01301207A (en) * | 1988-05-30 | 1989-12-05 | Kubota Ltd | Lining of inner face of pipe |
FR2635906B1 (en) * | 1988-08-25 | 1990-11-23 | Framatome Sa | INSTRUMENTATION DEVICE FOR THE HEART OF A PRESSURIZED WATER NUCLEAR REACTOR AND METHOD AND DEVICE FOR EXTRACTING AND PLACING THE INSTRUMENTATION DEVICE |
US5024808A (en) * | 1988-10-14 | 1991-06-18 | Westinghouse Electric Corp. | Combined support column and guide tube for use in a nuclear reactor |
US4937039A (en) * | 1989-01-17 | 1990-06-26 | Westinghouse Electric Corp. | Four pin mounting system for nuclear reactor control rod guide tubes |
US5488643A (en) * | 1994-05-11 | 1996-01-30 | Combustion Engineering, Inc. | Method and apparatus for supporting a shroud in a nuclear reactor |
US8483347B2 (en) * | 2007-04-10 | 2013-07-09 | Westinghouse Electric Company Llc | Upper internals arrangement for a pressurized water reactor |
PL2143996T3 (en) * | 2008-02-19 | 2013-12-31 | Balcke Duerr Gmbh | Collector for a high pressure device of a steam power array |
US8929505B2 (en) * | 2009-08-28 | 2015-01-06 | Terrapower, Llc | Nuclear fission reactor, vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system |
US20110150167A1 (en) * | 2009-08-28 | 2011-06-23 | Searete Llc, A Limited Liability Corporation Of The State Of Delaware | Nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system |
US9269462B2 (en) * | 2009-08-28 | 2016-02-23 | Terrapower, Llc | Nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system |
CN102598146B (en) * | 2009-08-28 | 2015-04-01 | 泰拉能源有限责任公司 | Method for assembling air-permeable nuclear fission fuel module |
US8712005B2 (en) * | 2009-08-28 | 2014-04-29 | Invention Science Fund I, Llc | Nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system |
US8488734B2 (en) * | 2009-08-28 | 2013-07-16 | The Invention Science Fund I, Llc | Nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system |
US11935663B2 (en) | 2012-05-21 | 2024-03-19 | Smr Inventec, Llc | Control rod drive system for nuclear reactor |
US9496057B2 (en) | 2012-08-06 | 2016-11-15 | Smr Inventec, Llc | Fail-safe control rod drive system for nuclear reactor |
Family Cites Families (11)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB552899A (en) * | 1941-10-24 | 1943-04-29 | Leonard Shakesby | Improvements in or relating to joints between pipes and fuel containers |
US2508655A (en) * | 1945-07-23 | 1950-05-23 | T & M Mfg Company | Clamping connector |
US3212979A (en) * | 1961-04-18 | 1965-10-19 | Westinghouse Electric Corp | Core support structure |
BE620146A (en) * | 1961-08-01 | 1900-01-01 | ||
GB1112346A (en) * | 1963-12-02 | 1968-05-01 | Atomic Energy Authority Uk | Improvements relating to nuclear reactors |
GB1112946A (en) * | 1965-08-10 | 1968-05-08 | Atomic Energy Authority Uk | Improvements relating to nuclear reactors |
US3481832A (en) * | 1967-04-14 | 1969-12-02 | Combustion Eng | Nuclear reactor core and control element arrangement |
US3595748A (en) * | 1968-01-24 | 1971-07-27 | Westinghouse Electric Corp | Nuclear reactor control device |
US3607629A (en) * | 1968-01-24 | 1971-09-21 | Westinghouse Electric Corp | Drive mechanism for control elements |
DE1764577B1 (en) * | 1968-06-28 | 1971-05-06 | Siemens Ag | CORE REACTOR CONTROL ROD DEVICE |
US3604746A (en) * | 1968-11-20 | 1971-09-14 | Combustion Eng | Nuclear reactor control element gripper and drive apparatus |
-
1972
- 1972-06-28 US US00266858A patent/US3849257A/en not_active Expired - Lifetime
-
1973
- 1973-06-14 CA CA174,071A patent/CA992672A/en not_active Expired
- 1973-06-27 FR FR7323490A patent/FR2202339A1/fr not_active Withdrawn
- 1973-06-27 SE SE7309077A patent/SE384289B/en unknown
- 1973-06-27 ES ES416637A patent/ES416637A1/en not_active Expired
- 1973-06-28 GB GB3089873A patent/GB1397723A/en not_active Expired
- 1973-06-28 JP JP7235373A patent/JPS5347880B2/ja not_active Expired
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE3023992A1 (en) * | 1979-07-02 | 1981-01-29 | Babcock & Wilcox Co | BRACKET FOR A CORE REACTOR CONTROL DEVICE |
Also Published As
Publication number | Publication date |
---|---|
DE2331355A1 (en) | 1974-01-10 |
JPS4943096A (en) | 1974-04-23 |
US3849257A (en) | 1974-11-19 |
JPS5347880B2 (en) | 1978-12-23 |
SE384289B (en) | 1976-04-26 |
CA992672A (en) | 1976-07-06 |
DE2331355B2 (en) | 1975-11-13 |
ES416637A1 (en) | 1976-12-01 |
FR2202339A1 (en) | 1974-05-03 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed [section 19, patents act 1949] | ||
PCNP | Patent ceased through non-payment of renewal fee |